ML15125A056

From kanterella
Jump to navigation Jump to search

E. I. Hatch Radioactive Effluent Release Reports for 2014, Enclosure 1
ML15125A056
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 12/31/2014
From: Betsill H
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML15125A049 List:
References
NL-15-0803
Download: ML15125A056 (87)
v • d • e


Text

Joseph M. Farley Nuclear Plant; Edwin I. Hatch Nuclear Plant; Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2014 Hatch Annual Radioactive Effluent Release Report for 2014

0SOUTHERN COMPANY E. L HATCH NUCLEAR PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-321 AND 50-366 FACILITY OPERA TING LICENSE NOS. DPR-57 AND NPF-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1, 2014 TO DECEMBER 31, 2014 Q

~~~~~Prepared by:I4) 4J//415 i

Reviewed by: v 3:.et

(.

0 77

0 ACKNOWLEDGEMENT OF OWNERSHIP The contents of this Annual Radioactive Effluent Release Report, contained herein, are true and accurate to the best of my knowledge. I understand that I am ultimately responsible for the information that has been captured within these pages.

Chemistry Manager 0

(9 78

0 SECTION TITLE PAGE 1.0 Liquid Effluents 1

1.1 Regulatory Requirements 1

1.1.1 Concentration Limits 1

1.1.2 Dose Limits 1

1.2 Effluent Concentration Limit 1

1.3 Measurements and Approximations of Total 2

Radioactivity for Liquid Radwaste 1.3.1 Total Radioactivity Determination for Liquid Radwaste 2

1.4 Measurements and Approximations of Total 4

Radioactivity for Groundwater Outfall -

Y22NOOBA 1.4.1 Total Radioactivity Determination for Groundwater 4

0 Ouffalls 1.5 Total Error Estimation 5

1.6 Liquid Effluent Release Data 6

1.7 Radiological Impact Due to Liquid Releases 7

1.8 Liquid Effluents - Batch Releases 7

1.9 Liquid Effluents - Continuous Releases 7

(9 79

0 1.10 2.0 2.1 2.1.1 2.1.2 2.1.3 2.2 2.2.1 2.2.2 2.2.2.1 2.2.2.2 2.2.2.3 2.2.3 2.3 2.4 2.5 2.6 3.0 3.1 3.1.1 3.1.2 TITLE Liquid Effluents - Abnormal Releases Gaseous Effluents Regulatory Requirements Dose Rate Limits Air Doses Due to Noble Gases in Gaseous Releases Doses to a Member of the Public Measurements and Approximations of Total Radioactivity Sample Collection and Analysis Total Quantities of Radioactivity, Dose Rates and Cumulative Doses Fission and Activation Gases Radiolodine, Tritium and Particulate Releases Gross Alpha Release Total Error Estimation Gaseous Effluent Release Data Radiological Impact Due to Gaseous Releases Gaseous Effluents - Batch Releases Gaseous Effluents - Abnormal Releases Solid Waste Regulatory Requirements Solid Radioactive Waste System Reporting Requirements P.AGF 7

28 28 28 28 28 29 29 30 30 30 31 31 33 34 34 34 58 58 58 58 0

(-

ii 80

0 SECTION TITLE PAGE 3.2 Solid Waste Data 59 4.0 Doses to Members of the Public Inside The 63 Site Boundary 4.1 Regulatory Requirements 63 4.2 Demonstration of Compliance 63 5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 68 5.1 Regulatory Requirements 68 5.2 Demonstration of Compliance 68 6.0 Meteorological Data 69 7.0 Program Deviations 70 7.1 Inoperable Liquid or Gaseous Effluent 70 Q*

Monitoring Instrumentation 7.1.1 Regulatory Requirements 70 7.1.2 Description of Deviations 70 7.2 Tanks Exceeding Curie Content Limits 70 7.2.1 Regulatory Requirements 70 7.2.2 Description of Deviations 70 7.3 Effluent Sample Analysis Exceeding Minimum 71 Detectable Concentration (MDC) 7.3.1 Regulatory Requirement 71 7.3.2 Description of Deviation 71 iii 81

SECTION TITLE PAGE 8.0 Changes to the Plant Hatch 71 Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements 71 8.2 Description of Changes 71 9.0 Major Changes to the Liquid, Gaseous or 72 Solid Radwaste Treatment Systems 9.1 Regulatory Requirements 72 9.2 Description of Major Changes 72 0

iv 82

TABLE UST OF TABLES PAGE 1-IA Liquid Effluents - Summation of All Releases 8

Unit I (Quarters 1, 2, 3 and 4) 1-lB Liquid Effluents - Summation of All Releases 9

Unit 2 (Quarters 1, 2, 3 and 4) 1-IC Liquid Effluents - Summation of All Releases 10 Site (Quarters 1, 2, 3 and 4) 1-2A Liquid Effluents - Unit I (Quarters 1, 2, 3 and 4) 11 1-2B Liquid Effluents - Unit 2 (Quarters 1, 2, 3 and 4) 14 1-2C Liquid Effluents - Site (Quarters 1, 2, 3 and 4) 17 1-3A Doses to a Member of The Public Due to Liquid 20 Releases Unit I (Quarters 1, 2, 3 and 4) 1-3B Doses to a Member of The Public Due to Liquid 21 Releases Unit 2 (Quarters 1, 2, 3 and 4) 0 1-4 Minimum Detectable Concentration -

22 Liquid Sample Analysis 1-5A Liquid Effluents - Batch Release Summary 23 Unit I 1-5B Liquid Effluents - Batch Release Summary 24 Unit 2 (9

v 83

TABLE LIST OF TABLES PAGE 1-GA Liquid Effluents - Abnormal Release 25 Summary Unit I 1-6B Liquid Effluents - Abnormal Release 26 Summary Unit 2 1-6C Liquid Effluents - Abnormal Release 27 Summary Site 2-IA Gaseous Effluents - Summation of All 35 Releases - Unit I (Quarters 1, 2, 3 and 4) 2-11B Gaseous Effluents - Summation of All 36 Releases -Unit 2 (Quarters 1, 2, 3 and 4) 2-IC Gaseous Effluents - Summation of All 37 Releases - Site (Quarters 1, 2, 3 and 4) 2-2A Gaseous Effluents - Elevated Releases 38 Unit I (Quarters 1, 2, 3 and 4) 0 2-2B Gaseous Effluents - Elevated Releases 39 Unit 2 (Quarters 1, 2, 3 and 4) 2-2C Gaseous Effluents - Elevated Releases 40 Site (Quarters 1, 2, 3 and 4) 2-3A Gaseous Effluents - Ground Level Releases 43 Unit I (Quarters 1, 2, 3 and 4) 2-3B Gaseous Effluents - Ground Level Releases 44 Unit 2 (Quarters 1, 2, 3 and 4) 2-3C Gaseous Effluents - Ground Level Releases 46 Site (Quarters 1, 2, 3 and 4) 2-4A Air Doses Due to Noble Gases in Gaseous 48 Releases - Unit I (Quarters 1, 2, 3 and 4) 1 vi 84

"Jr'Aol I IC'l"J~tl "r J~lI*

CA C

Q 2-4B Air Doses Due to Noble Gases in Gaseous 49 Releases-Unit 2 (Quarters 1,2, 3 and 4) 2-5A Doses to a Member of the Public Due to 50 Radioiodine, Tritium, and Particulates in Gaseous Releases - Unit I (Quarters 1, 2, 3 and 4) 2-5B Doses to a Member of the Public Due to 51 Radioiodine, Tritium, and Particulates In Gaseous Releases - Unit 2 (Quarters 1, 2, 3 and 4) 2-6 Minimum Detectable Concentration -

52 Gaseous Sample Analyses 2-7A Gaseous Effluents - Batch Release 53 Summary Unit I 2-7B Gaseous Effluents - Batch Release 54 Summary Unit 2 2-8A Gaseous Effluents - Abnormal Release 55 Summary Unit 1 2-8B Gaseous Effluents - Abnormal Release 56 Summary Unit 2 2-8C Gaseous Effluents - Abnormal Release 57 Summary Site 3-1 Solid Waste and Irradiated Fuel Shipments 60 4-1 Doses to a Member of the Public Due to 64 Activities Inside The Site Boundary v(

85

ATTACHMENT APPENDIX A APPENDIX B TM' P&WF 73 Carbon-14 Summary of Groundwater Protection Program 75 vii 86

0 1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration Limits The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 E-04 microcuries/ml total activity.

1.1.2 Dose Limits The dose or dose commitment, to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS, shall be limited:

a.

During any calendar quarter, to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b.

During any calendar year, to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

1.2 Effluent Concentration Limit ECL values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters, 1-131, tritium, Sr-89, Sr-90 and Fe-55, are taken from 10 CFR Part 20, Appendix B, Table 2, Column 2.

A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 2, Column 2.

For dissolved or entrained noble gases in liquid radwaste, the ECL is I E-04 uCi/ml total activity.

For gross alpha in liquid radwaste, the ECL is 2E-09 uCi/ml.

Furthermore, for all the above radionuclides, or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B.

The method utilizing the ECL fraction to determine liquid radwaste release rates and effluent radiation monitor set points is described in Subsection 1.3 of this report.

1 87

0 The method utilizing the ECL fraction to determine the dose released from groundwater outfalls is described in Subsection 1.4 of this report.

1.3 Measurements and Approximations of Total Radioactivity for Liquid Radwaste Prior to the release of any tank containing liquid radwaste, following the required recirculations, samples are collected and analyzed in accordance with the Edwin 1. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3.

A sample from each tank planned for release is analyzed for principal gamma emitters, 1-131, and dissolved and entrained noble gases, by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks released.

Liquid radwaste sample analyses are performed as described in Section 1.3.1.

1.3.1 Total Radioactivity Determination for Liquid Radwaste MEASUREMENT 0

1. Gamma Isotopic
2. Dissolved or entrained noble gas
3. Tritium
4. Gross Alpha
5. Sr-89 & Sr-90 FREQUENCY Each Batch Each Batch Monthly Composite Monthly Composite Quarterly Composite Gamma Spectroscopy with computerized data reduction Gamma Spectroscopy with computerized data reduction Distillation and liquid scintillation counting Gas flow proportional counting Chemical separation and gas flow proportional or scintillation counting Chemical separation and liquid scintillation counting METHOD
6. Fe-55 Quarterly Composite (9

2 88

Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2 keV or lower. The detectors are shielded by four inches of lead. A liquid radwaste sample is typically counted for 2000 seconds and a peak search of the resulting gamma ray spectrum is performed. Energy and net count data for all significant peaks are determined and a quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present. Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed offsite.

The radionuclide concentrations determined by gamma spectroscopic analysis of samples taken from tanks planned for release, in addition to the most current sample analysis results available for tritium, gross alpha, Sr-89, Sr-90 and Fe-55, are used along with the corresponding ECL values to determine the ECL fraction for these tanks. This ECL fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the ODCM are not exceeded.

A monitor reading in excess of the calculated setpoint will result in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.

Radionuclide concentrations, safety factors, dilution stream flow rate, and the liquid effluent radiation monitor calibration factor, are entered into the computer and a pre-release printout is generated. If the release is not permissible, appropriate wamings will be displayed on the computer screen. If the release is permissible, it is approved by a qualified Chemistry Technician. The pertinent information is transferred manually from the pre-release printout to a one-page release permit, which is forwarded to Radwaste Operations. When the release is completed, the release permit is returned from Radwaste Operations to Chemistry with the actual release data provided. These data are input into the computer and a post-release printout is generated. The post-release printout contains the actual release rates, the actual release concentrations and quantities, the actual dilution flow, and the calculated doses to a Member of the Public.

3 89

0 1.4 Measurements and Approximations of Total Radioactivity for Groundwater Outfalls - Y22NO03A/12B and Y22NOOSA Samples are collected and analyzed in accordance with the Edwin I. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3. Weekly, monthly and quarterly composites are prepared for analysis by extracting aliquots from each ouffall's automatic sampler, which collects a composite sample over a seven-day period. Sample analyses are performed as described in Section 1.4.1.

1.4.1 Total Radioactivity Determination for Groundwater Outfalls MEASUREMENT

1. Gamma Isotopic FREQUENCY METHOD Weekly Composite
2. Tritium Weekly Composite 0
3. Gross Beta *
4. Sr-89 & Sr-90 **

Quarterly Composite Quarterly Composite (as required)

Gamma Spectroscopy with computerized data reduction Distillation and liquid scintillation counting Chemical separation and gas flow proportional or scintillation counting Chemical separation and gas flow proportional or scintillation counting

  • Gross Beta analysis is used for sample screening.
    • If the Gross Beta analysis yields a detectable value above background, a Sr-89/90 analysis will be performed.

(9 4

90

Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2 keV or lower. The detectors are shielded by four inches of lead. A weekly composite sample Is typically counted to Environmental MDC's and a peak search of the resulting gamma ray spectrum is performed.

Energy and net count data for all significant peaks are determined and a quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

Trtium, Gross Beta, Sr-89 and Sr-90 are, in some cases, analyzed offsite.

The radionuclide concentrations determined by gamma spectroscopic analysis of the weekly composite sample, in addition to the most current sample analysis results available for tritium, gross beta, Sr-89 and Sr-90, are used along with the corresponding ECL values to determine the ECL fraction for these composite samples. This ECL fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate projected dose released.

Radionuclide concentrations, safety factors and dilution stream flow rate are entered into the computer and a pre-release printout is generated for each release period. When the release period is complete, the release permit is updated with the actual release data collected during the release period. These data are input into the computer and a post-release printout is generated. The post-release printout contains the actual release rates, the actual release concentrations and quantities, the actual dilution flow, and the calculated doses to a Member of the Public. Cumulative dose results are tabulated along with the percent of the ODCM limit for each release period, for the current quarter and year.

1.5 Total Error Estimation The maximum error associated with volume and flow measurements, based upon plant calibration practice, is estimated to be + or - 10%. The average error associated with counting is estimated to be less than + or - 15%. Therefore, the total error estimation is + or - 18%.

91

0 1.6 Liquid Effluent Release Data Regulatory Guide 1.21, Tables 2A and 2B are found in this report as Table 1-1A for Unit 1, Table 1-1B for Unit 2 and Table 1-1C for the site; and Table 1-2A for Unit 1, 1-2B for Unit 2, and Table 1-2C for the site. Typical liquid minimum detectable concentrations (MDC's) used for analyses are found in Table 1-4.

The values for the four categories of Tables 1-1A, 1-1 B, and 1-1C, are calculated and the Tables completed as follows:

1.

Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective quarter.

2.

Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period.

3.

Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured by germanium spectroscopy using a one liter sample from each liquid radwaste batch. The measured concentrations are used to calculate the total release and the average diluted concentration during the period. Radioisotopes of iodine in any form are also determined during the isotopic analysis for each batch; therefore, a separate analysis for possible gaseous forms is not performed because it would not provide additional information.

4.

Gross alpha radioactivity - The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity.

0 6

92

0 1.7 Radiological Impact Due to Liquid Releases Doses to a Member of the Public due to radioactivity in liquid effluents were calculated in accordance with the Offsite Dose Calculation Manual. Results are presented in Table 1-3A for Unit 1, and 1-3B for Unit 2, for all four quarters.

1.8 Liquid Effluents - Batch Releases Batch Release information for Units 1 and 2 is summarized in the following tables:

Unit 1 Liquid Batch Releases:

Table 1-5A Unit 2 Liquid Batch Releases:

Table 1-5B 1.9 Liquid Effluents - Continuous Releases Continuous Release information is summarized in the following tables:

Unit I Liquid Continuous Releases:

Table 1-2A Unit 2 Liquid Continuous Releases:

Table 1-2B Hatch Site Conitinuous Releases:

Table 1-2C Q1.10 Liquid Effluents - Abnormal Releases There were no abnormal liquid releases for this reporting period.

0 7

93

Table 1-1A 0

Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Uquid Effluents - Summation Of All Releases Unit* 1 Starting: 1-3an-2014 Ending: 31-Dec-2014 Type of Elfluent A. Fission And Activation Products

1. Total Release (not Including bitium, gases, alpha)
2. Average diluted concentration durng period
3. Percent of Applicable Limit B. Tritlum
1. Total Release
2. Average diluted Concentration during period
3. Percent of Applicable Limit C. Dissolved and Entrained Gases O
1. Total Release
2. Average diluted Concentration during period
3. Percent of Applicable Limit 0: Gross Alpha Radioactivity
1. Total Release E: Waste Vol Release (Pre-bilution)

F. Volume of Dilution Water Used Units IST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies uO/mL Cujries uO/mL Curies uC/mL Curies Liters Liters 5.38E-03 g.31E-09 1.77E+01 3.06E-05 6.57E-05 1.14E-10 0.O0E+00 2.89E+06 5.78E+08 3.22E-03 6.15E-09 4.65E+00 8.8E-06 1.67E-05 3.19E-11 O.OOE+00 2.39E+06 5.23E+08 2.45E-03 2.13E-04 4.73E-09 1.97E-09 3.81E+00 1.03E+00 7.34E-06 1.06E-05 2.04E-1 1 0.00E+00 9.51E-06 4.49E-06 4.15E-11 0.0E0 2.31E+06 4.90E+05 5.19E+08 1.08E+08 0

  • Applicable limits are expressed In terms of dose. See Tables 1-3A and 1-3B of this report.

8 94

Table 1-15 Q

Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Summation Of All Releases Unit: 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarte 4TH Quarter A. Fission And Activation Products

1. Total Release (not Induding tritlum, gases, alpha)

Curies 2.55E-03 5.75E-04 2.92E-04 3.90E-03

2. Average diluted concentration during period uCI/mL 6.11E-10 1.28E-10 S.SIE-11 1.06E-09
3. Percent of Applicable Limit B. Tritium
1. Total Release Curies 4.04E+00 1.22E+00 3.53E+00 2.70E+00
2. Average diluted Concentration during period uC/mL 9.68E-07 2.70E-07 6.67E-07 7.35E07
3. Percent of Applicable Umit C. Dissolved and Entrained Gases O 1. Total Release Curies 2.68E-04 8.85E-05 3.03E-05 1.tSE-04
2. Average diluted Concenltration during period uC/mL 6.42E-11 1.97E-11 5.71E-12 3.13E-11
3. Percent of Applicable Limit a

a a

D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 0.00E+00 O.00E+00 O.OOE+O0 E: Waste Vol Release (Pre-Dilution)

Liters 3.94E+06 4.13E+06 3.65E+06 3.37E+06 F. Volume of Dilution Water Used Uters 4.17E+09 4.50E+09 5.30E+09 3.67E+09 0

  • Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

9 95

Table 1-1C 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Uquid Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Type of Effluent A. Fission And Activation Products

1. Total Release (not Iucldng tritum, gases, alpha)
2. Average diluted concentration "rig period
3. Percent of Applicable Umit B. Tritlum
1. Total Release
2. Average diluted Concentration during period
3. Percent of Applicable Umit C. Dissolved and Entrained Gases O

L Total Release

2. Average diluted Concentration during period
3. Percent of Applicable Umit D: Gross Alpha Radioactivity
1. Total Release E: Waste Vol Release (Pre-Dilution)

F. Volume of Dilution Water Used Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies ui/mL Cures Curies ua/mL 7.93E-03 1.67E-09 2.17E+01 4.58E-06 3.33E-04 7.02E-11l 6.83E+06 4.75E+09 3.79E-03 7.55E-10 5.87E+00 1.17E-06 1.OSE-04 2.10E-11 0

0.OOE+0O 6.51E+06 5.02E+09 2.74E-03 4.72E-10 7.34E+00 1.26"-6 4.09E-05 7.03E-12 0.OOE+00 4.11E-03 1.09E-09 3.73E+00 9.85E-07 1.20E-04 3.16E-11 0.00E+00 Uters Uters 5.95E+06 3.86E+06 5.81E+09 3.78E+09 (9

  • Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.

10 96

0 Table 1-2A Hatch Nuclear Plant RADIOACTnVE EFFLUENT RELEASE REPORT - 2014 Uquid Emuents Unit: 1 Starting: 1-3an-2014 Ending: 31-Dec-2014 Continuous Mode Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+O0 Curies O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Nudlides Released Fission & Activation Products No Nuclides Found Tritium No Nudides Found Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity No Nudlides Found Curies Curies O.OOE+OO O.OOE+00 O.OOE+OO 0.00E+00 O.OOE+OO O.OOE+00 O.OOE+OO 0.0012+00 0

0 Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

11 97

Table 1-2A 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Uquid Effluents Unit: 1 Starting: 1-3an-2014 Ending: 31-Dec-2014 I

Batch Mode Nudides Released Fission & Activation Products Co-60 Sr-89 Zn-65 Sb-124 Cs-134 Nb-97 Au-199 Mn-54 TC-99M Fe-59 Zn-69M Sr-90 Sr-92 O

Cr-Si Sb-122 CO-58 Fe-55 Nb-95 Cs-136 1-131 Cs-137 Mn-S6 Na-24 AS-76 Ag-I10M Total For Period Unit 1ST Quarter 2ND Quarter 3RD Quarter 41H Quarter curias Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies curias Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1.84E-03 0.006+00 5.03E-04 5.13E-06 5.52E-OS 8.92E-OS 2.49E-06i 9.98E-04 7.61E-07 3.39E-OS 4.14E-OS 9.60E-05 4.93E-06 4.78E-04 2.91E-06 2.91E-04 4.42E-04 1.94E-06 1.35E-05 1.25E-05 1.72E-04 6.87E-05 1.49E-04 1.33E-OS 6.69E-05 1.64E-03 1.19E-04 1,91E-04 3.69E-06 1.92E-06 9.52E-06 0.00E+00 2.36E-04 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.801-05 O.OOE+00 6.86E-O5 2.18E-04 4.90E-07 O.OOE+00 0.00E+00 2.58E-04 O.OOE+00 4.47E-04 0.00E+00 0.00E+00 1.12E-03 0,00E+00 8.77E-05 0.OOE+00 0.O0E+00 0.00E+00 0.00E+00 1.57E-04 3.70E-07 0.00E+00 2.74E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.68E-05 4.59E-04 0.00E+00 O.OOE+00 0.00E+00 1.84E-04 7.26E-06 3.92E-04 6.16E-06 0.006+00 1.47E-04 0.00E+00 1.70E-05 0.00E+00 0.00E+00 O.00E+00 0.OOE+00 1.31E-05 0.00E+00 O.OOE+00 0.001+00 0.00E+00 O.OOE+0O 0.00E+00 O.OOE+00 2.00E-06 1.74E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.11E-05 O.OOE+00 6.10E-06 0.00E+00 0.00E+00 2.13E-04 1.03E+00 O.OOE+00 4.49E-06 4.49E-06 Curies 5.38E-03 3.22E-03 2.45E-03

Tritium, H-3 Curies 1.77E+01 4.65E+00 3.81E+00 Dissolved And Ent-alned Gases Xe-133 Xe-135 Total For Period Curies Curies Curies 3.26E-06 5.63E-06 0.00E+00 6.25E-05 1.11E-05 1.06E-05 6.57M-05 1.67E-05 1.061-05 0

Zeroes In this table Indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

12 98

Table 1-2A 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nudides Released Gross Alpha Radloactl No Nuclides Found

'ity unit Curies OoOOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 0

(9 Zeroes In this table Indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

13 99

0 Nudides Released Fission & Activation Products Sr-89 Total For Period Triutium H-3 Dissolved And Entrained Gases No Nudides Found Gross Alpha Radioactivity No Nucides Found Table 1-2B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit, 2 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Unit 1ST Qumater 2ND Quarter 3RD Quarter 4TH Quarter Curies 2.04E-05 1.21E-04 0.OOE+00 O.OOE+00 Curies 2.04E-05 L1E-04 0.00E+00 0.00E+00 Curies 1.50E-02 1.14E-02 6.25E-03 7.54"-03 Curies Curies O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

(-

Zeroes In this table Indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

14 100

Table 1-28 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit-2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released Fission & Activation Products Zn-65 As-76 1-131 Zn-69M Na-24 Cr-Si FE-59 Nb-97 Sr-91 Co-60 1-133 Cs-134 Sr-89 Sr-9O 133-140 La-140 Ag-110101 Mn-56 Y-92 Cs-137 TC-9914 Fe-55 Mn-54 CO-58 Y-91M Ce-L41 Sr-92 Unit Curies Curies Curies Curies Curies Caures Curies Caries Curies Curies Curies Curies Curies Curies curios curies Curies Curies Curies Curies Cures Curies Curies Curies Curies Curies Curies C

1ST Quarter 1.74E-04 9.93E-06 2.67E-05 5.36E-05 2.25E-04 2.18E-05 0.00E+00 1.05-E04 2.46E-05 4.60E-04 2.42E-OS 1.48E-05 3.03E-04 1.52E-05 3.73E-05 5.98E-05 4.76E-05 5.87E-05 7.77E-05 7.45E-05 3.19E-05 5.59E-05 4.16E-04 1.93E-04 S.08E-06 3.68E-06 9.29E-06 2.53E-03 4.02E+00 7.86E-05 1.89E-04 0.OOE+OD 2.68E-04 6.22E-05 O.OOE+00 5.00E-06 3.57E-06 7.20E-05 2.01E-05 0.00E+00 1.84E-05 0.OOE+00 1.20E-04 3.99E-06 O.OOE+00 3.80E-05 2.49E-06 O.OOE+0O 3.58E-06 0.001+00 0.00E+00 0.00E+00 1.56E-05 5.01E-06 0.00E+00 6.23E-05 2.21E-05 0,00E+00 O.OOE+00 O.OOE+00 4.55E-04 1.20E+00 1.77E-05 7.08E-05 0.00E+00 I.85E-05 4.21E-05 4.03E-04 O.OOE+00 2.24E-05 1.18E-06 1.86E-05 O.OOE+00 2.63E-04 1.57E-06 2.59E-04 O.00E+00 6.88E-0S 0.00E+00 5.46E-06 1.02E-05 1.79E-05 0.00E+00 8.09E-05 1.36E-04 8.02E-04 0.00E+00 2.05E-OS 2.89E-06 O.OOE+00 O.OOE+00 5.92E-04 9.98E-06 0.00E+00 0.00E+00 1.01E-04 O.OOE+00 9.40E-05 2.28E-06 8.56E-06 0.00E+00 3.68E-04 O.OOE+00 9.37E-05 2.78E-05 8.06E-05 O.OOE+00 4.78E-05 O.0OE+00 O.OOE+00 4.76E-05 3.29E-04 1.01E-05 1.40E-04 O.OOE+00 2.41E-05 0.00E+00 2.62E-05 O.OOE+00 3.60E-05 2.92E-04 3.90E-03 2ND Quarter 3RD Quarter 4TH Quarter Total For Period Tritium H-3 Curies 3.53E+00 2.69E+00 Dissolved And Entrained Gases Xe-133 Xe-135 Xe-131M O

Total For Period Curies curies curies Curies 3.96E-06 3.20E-05 2.63E-05 3.68E-05 0.00E+00 4.621-05 3.031-05 1,1SE-04 Zeroes In this table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

15 101

Table 1-2B 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nuclides Released Unit Gross Alpha Radioactivlty No Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 0

C9 Zeroes in this table Indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

16 102

Table 1-2C 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Continuous Mode 1ST Quarter 2ND Quarter 3RD Quaster 4TH Quarter Nuclides Released Fission & Activation Products Sr-89 Total For Period Tritium H--3 Dissolved And Entrained Gases No Nuclides Found Unit curies 2.04E-05 1.21E-04 O.OOEeOD O.OOE+00 Curies 2.04E05S 1.21E-04 0.801+00 O.OOE+00 curies Curies curies 1.50E-02 O.OOE+OO O.OOE+00 1.14E-02 O.OOE.OO 0.O0E+00 6.25E-03 O.OOE+00 7M5E-03 0.00E+00 Gross Alpha Radioactivity No Nuclides Found O.OOE+00 0.00E+00 0

(9 Zeroes In this table Indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

17 103

Table 1-2C 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Uquid Effluents Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Batch Nudides Released Fission & Activation Products Cs-137 Cr-Si Na-24 Zn-6914 tMn-S4 1-133 Ce-141 Cs-134 Y-91M CD-60 Sr-92 1-131 Mn-56 OCO-58 As-76 Au-199 Cs-136 La-140 5r-90 Nb-95 Fe-59 Sr-89 Ag-1ION Ba-140 Y-92 Zn-65 Nb-97 sr-9i Fe-55 Tc-991 Sb-124 Total For Period Unit Curies Curies QCies Curies Curies Curies Curies Curies Curies Curies Curies Curies curies Curies curies Curies Curias Curies curies Curies Curies Curies Curies Curies Curies curies Curies Curies Curies Curies 1ST Quarter 147E-04 5.00E-04 3.74E-04 9.SOE-05 1.41E-03 2.42E-05 3.68E-06 7.00E-05 5.08-E06 2.30E-03 1.42E-05 3.92E-05 1.27E-04 4.85E-04 2.32E-05 2.49--06 1.35E-05 5.98E-05 1.11E-04 1.94E-06 33M9-05 2.91E-06 3.03E-04 1.15E-0, 3.73E-05 7.77E-05 6.77E-04 1.94E-04 2.46E-05 4.98E-04 3.27E-05 5.13E-06 7.91E-03 2.17E+01 2ND Quarter 2.73E-04 4.81E-05 5.19E-04 3.57E-06 2.98E-04 3.99E-06 0.00E+00 1.92E-06 O.OOE+O0 1.76E-03 0.00E+00 5.00E-06 0.00E+00 9.08E-05 O.OOE+00 0.OOE+00 O.OOE+00 3.58E-06 2.49E-06 4.90E-07 O.OOE+00 O.OOE+00 1.57E-04 O.OE+00 O.OO+O0 O.OOE+00 2.53E-04 2.79E-05 O.OOE+00 2.18E-04 5.01E-06 3.69E-06 3.67E-03 5.86E+00 Mode 3R1D Quarter 4TH Quarter 2.12E-04 9.17E-05 0.00E+00 6.88E-05 3.94E-04 2.65E-04 2.74E-06 2.63E04 2.04E-04 3.42E-04 0.00E+00 2.05E-05 0.00E+00 2.62E-05 2.89E-06 0.00E+00 O.OOE+00 2.41E-05 1.26E-03 9.48E-04 0.00-+00 3.60E-05 1.14E-06 1.86E-05 7.26E-06 3.68E-04 4.70E-05 1.42E-04 6.16E-06 2.24E-05 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 9.40E-05 9.98E-06 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 5.46E-06 O.OE+00 O.OOE+00 0.00E+00 5.92E-04 2.28E-06 8.56E-06 O.OOE+00 1.01E-04 O.00E+00 9.37E-05 13M-04 4.20E-4 1.02E-05 1.79E-05 0.00E+00 8.09E-05 4.59E-04 1.74E-05 3.70E-07 4.78E-05 O.OOE+00 0.002E00 2.74E-03 4.11E-03 Tritium H--3 curies 7.33E+00 3.72E+00 0

Zeroes in this table indicates that no radloactivty was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

18 104

Table 1-2C 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Batch Mode 15s Quarter 2ND Quarter 3RD Quarter 4TH Quarter Nuclides Released Dissolved And Entrained Gases Xe-131M Xe-133 Xe-135 Total For Period Gross Alpha Radioactivity No Nuclides Found Unit Curies O.OOE+0O O.OOE+OO O.OOE+OO Curies 8.19E-05 2.33E-05 3.96E-06 Curies 2.52E-04 8.19E-05 3.69E-05 Curies 3.33E-04 1.03E-04 4.09E-05 4.62E-05 3.20E-05 4.13E-05 1.2015-04 0.00E+00 Curies 0.00E+00 O.OOE+00 O.OOE+00 0

(-

Zeroes in thWs table indicates that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

19 105

0 Table 1-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a munber of the public due to Liquid Releases tidn I

Stating: 1-3an-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Oa*g 0004 tLnt Units Lung 5.0WE+00 mian ThyOrd 5-06.0 mRen Kkh"e S.O**ow MRem TO Bdny 501E4-00 Milaen Live 5.OOE+00 tr"n Done 5.00+00 mRem

( 1 0

Ln U5.00+00 mRern iST Qtr

!b O0C0 2ND Qir

% ODCI 3R0 Qtr

% 000C 4eHMQtr

% 00C4 2.77E-04 5.54E.03 1.75E-04 3.50-03 1.232E04 2.45E.03

[.43E-05 2.E-04 2.22E-04 4.44E-03 3.512E05 7.03E.04 2.62E-05 5.24E.04 7.142E06 1.43,04 7403E-04

.4IE-02 5.00E.04 1.OE-02 3.37E-04 6.74E-03 3.34E-05 6.68"-04 1,32E-03 9.8*E-02 9.78E-04 6.52-02 6.65E-04 4.43E-02 6.26E,05 4.17E-03 1.71E-03 3.42E-02 1.39E-03 2.78E-02 9.441E-04 1.09E-02 8.27E-0S 1.65E-3 1.1OE-03 2.20r-02 9.35E-04 1.87.-02 6,35E-04 1.27E.02 4.841E-05 969-04 1.46E-03 2.93C-02 9.,7E-04 1.91E102 6.33E-04 1.27E-02 1.06E.04 2.12E.03 Cumulative Doses per Year D004 tmt Unrit

.hymid 1.O0+01 macrn To*e Body 3.06+*00 m0 en KW"ney 1.006.0*

mRcn Liver 1.o00+01 m"em Lung 1.00E+01 micmr Done 1.00E+01 miecn 83-1) 1.006+01 nltem 2.91E-04 3.03E-03 1.57E-03 4.13E-03 5.89E-04 2.72E-03 3.16E-03

%OO)CM1 Receilar 2.91E-03 MAX INDIVIDUAL LIQUID I Adull I.OIE-01 MAX INDIVIDUAL IUQUID I Adult 1.57E-02 MAX INDIVIDUAL LIQUID / Adult 4.13E-02 MAX INDIVIDUAL ULQUID I Adult 5.80-03 MAX INDIVIDUAL LIQUID / Adult 2.72E&02 MAX mDmoUAL LIQUID I Adult 3.16E602 MAX INDIVIDUAL UQUID/ MA

'kmit Ann Cumr Organ Lk Dose Ann Curn Tot Body UIq Dose Ann Cumr Organ Ltc Dose Ann Cum Organ ULq Dose Ann Cam Organ Liq Dose Ann Cumr Organ Uq Dose Ann Cn Organ Lg Doie 20 0

106

0 Table 1-3B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014' Doses to a member of the public due to Uquld Releases Unit: 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Organ OCM L.t Units TId 5.00E+00 mITA=

G1-LB 5.00 nIte Lung 5.00E+00 ndtem on 5.00E+00 Meueni Total Body 1.50E+O0 strn Kdney 5.00E+01) niRem

( e 5.00E+00 rnRern 1sT Wu.

% 0o0m 2N"DQr

% 0004 3'O Qtr

% ODC0 4TH Qtr

% o0a4 2.27E-04 4.54E-03 4.561-0 9.1*E-04 3.75E-05 7301-04 1.60E-4 119E-03 5.51E-04 1.101-02 1.131-04 2.26E-03 1.40E-04 2.79E-03 7,1BE-04 1.44E.02 8.71e-05 1.741-03 1.97E-05 3.94E-04 4.95E-05 9.90E-04 7.39M-05 1.41E-03 4.27E-04 8.54E-03 9.69E-05 1.94E-03 1.55E-04 3.09E-03 4.39E04 8,77E-03 4.60E-04 3.07E-02 9.76E-05 5.84E-03 1.74E-04 1.16E.02 431&E-04 3.00E-02 2.525-04 S.05E-03 5.55E-05 1.11E-03 1.0E-04 2.03E-03 2.84E-04 5.68E,03 6391!04 1,28E-02 L25E-04 2.49E-03 2.31E-04 4.62E503 6.66E.04 1.33E-02 Cumulative Doses per Year op0 oCM4 List Units Year to Ending Date GC-LUi

.0E+01 mitRem 1.52E-03 Total Body 3.00E+00 niern 1.17E-03 Lung 1.00E+01 sterm 2.30E04 Bone 1.OE+01 sitrm 1.12E-03 Liver I.0E5+01 mR*ni 1,66E-03 Thy.od 100E+01.01 r11 4.70E-04 Kidne 1.001+01 nMecn 6.93E.04

%t OCM ReCeptor

.S2E-02 MAX INDIVIDUAL LIQUID I Adult 3.91E-02 MAX INDIVIDUAL LIQUID / Adult 2.30E-03 MAX INDIVIDUAL LIQUID / Adult 1.12E-02 MAX INDIVIDUAL LIQUID / Adult 1.66E102 MAX INDIVIDUAL LIQUID / Adult 4.70E-03 MAX INDIVIDUAL LIQUID I Adult 6.93E-03 MAX INDIVIDUAL LIQUID / Adult Ann Curn Organ LIq Dose Ann Cumr Tot Body Uq Dose Ann Curn Ofan Liq Dose Ann Care Om an Liq Dose Ann Cun Orpn Uq Dose Ann Curn Organ LIt Dose Ann Can Orn LIq Dose 21 0

107

Table 1-4 E. L HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT-2014 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES STARTING: 1-Jan.2014 ENDING: 31-Dec-2014 RADIONUCLIDE MDC UNITS Mn-54 1.97E-08 uCi/ml Fe-59 3.94E-08 uCi/ml Co-58 1.59E-08 uCi/ml Co-60 1.72E-08 uCi/ml Zn-65 2.92E-08 uCi/ml Mo-99 1.20E-07 uCi/ml Cs-134 1.75E-08 uCi/ml Cs-1 37 1.62E-08 uCi/ml Ce-141 1.92E-08 uCi/ml Ce-144 8.83E-08 uCi/ml 1-131 1.43E-08 uCi/ml Xe-135 1.03E-08 uCi/mi Fe-55 2.34E-08 uCi/ml Sr-89 1.44E-08 uCi/ml Sr-90 8.50E-09 uCi/ml O

H-3 6.OOE-07 uCi/ml The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

0 108

0 Table I-5A Hatch Nucleaw Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Batch Release Suniniary Unit: I Stairting: 1-Jan-2014 Ending: 31-Dec-2014 Uqutd Rreleaes units L Number of batch releases

2. ToMAl Ume i*

r Batch releases

("mutes)

3. Mainumn time period for a bath release (Minutes)
4. Average time period for a batch release (Minutes)

S. Mbfnim unme period for a batch rele (minutes)

O

6.

Average strearn flow during p&Ios Srease of iquid efte Into a flowbigstre*

m (CFS)

D ate obtained from United States Geological SurveY (USGS) websile SIT Qutrter 2ND Quart-3RD Qurter 4Th Quamter Year Totas s0 63 61 14 218 I.IOE+04 9.87E+03 9.19E+03 1.91E+03 3.19E+04 i.80E+02 1.82E+02 2.00E+02 1.65E+02 2.00E+02 1.37E+02 1.57E+02 1.51E+02 1.36E+02 1.47E+02 7.20E-01 8.50m+01 9..0E+01 9.10E+01 7.20E+01 0.00E+00 O.004E00 D000E+00 0,00E+00 0.008+00 0

109

0 Table 1-58 Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Batch Release Summary Unit-2 Starting: 1-oan-2014 Ending: 31-Dec-2014 Lkuid Releases Units L. Nmwber of batch releases

2. Total time period for Batch releases (Minues)
3. Ma tium Me period for a batch release (Mhutes)
4. Average tkne period for a batch release

( Minutes )

&. Mfninum lime pe.od for a batch release (Minutes)

O

6. Average slream flow during periods of release of liuld eflu*et Into a flow" streamI (CFS)
  • Data obtained (am Unied States GeoblcaM Survey (USGS) website UTr qMWte 2ND Quarte 3RD Quarter 4TH Qu~re wsTOW7tils 21 9

36 27 93 2.47E+03 8.76E+02 3.99E+03 2.75E.403 1.01E+04 1.95E+02 Ll52E+02 1.34E-+02 1.28E+02 1.95E+02 M.18202 9.73E+01 1.I1E+02 L.02E.02 1.09E+.02 7.902401 7.70E-4-01 7.90E+01 7.802+01 7.70E+01 0.0o0+00 O.OOE+00 0.08E+00 0.00E+00 0.00f+00 24 (9

110

0 Table 1-GA Hatch Nuclear Plant RADIOACrIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Abnormal Release Summary Unit. I StWtin: 1-Ian-2014 Ending: 31-DeC-2014 L Number of Releases

2. Total lime For Al Release
3. Maxhmun Time For A Release
4. Average Time For A Release
5. Minmum Time For A Release
6. Total actty foe relases anti isvquite 2ND Queter 3RD Queater 4TH quiter Year Totws 0

0 0

0 0

(Minues) 0.00E+00 0.00f400 0.001+00 0.00E+00 0.0w÷+00 (Minutes) 0,00E+00 MO0E000 0.00E+00 0.O0+00 O.OO+00 (M

.nutes) 0.00E00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (Minutes )

0.000E+0 0.06+00 ODE600 0.00E+00 0.06+00 (Outs) 0.00E+00 000E+00 0.006+00 0.00E+00 0.00E+00 0

2I C) 111

0 Table 14511 hatch Nuclear Klant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Uiquld Effluents - Abnormal Release Summary hUnit; 2 Stafllng: 1-ian-2014 Ending: 31-Pnc-2014 Liquid Releases L MNutber oft tekases

2. Total Tr*e Fr AD Reasses
3. MaAdmum lmw For A Release
4. Average Time For A Release
5. Minimum Th* For A Release
6. Tota activiy rr aD Sdeases 0

units 1ST Qusw 2ND QumAtr 3RD Quter 4TH Quatsr Tar Totals 0

0 0

0 0

(Mflzte) 0.00600 0.0064.00 Q0.00+00 0,006.00 0.006+00 (Mmnutes) 0*0E+00 0.00E+00 0.00+00 0.006.40 0.00E+00

( mut )

O.OOE+00 0.00B+00 0.006+00 0.00E+00 0.00E+00 (Minutes) 0.00E+00 0.006+00 0.00E+00 0A0E+00 0.00E+00

( urine) 0.o00,+.00 O.0011+00 OOOE+00 MOE+O0 0.00E+00 25 0

112

0 Table 1-6C Lkj Ileloome

1. Numbe of Relee
2. Tota Time Fo ADl Releases
3. Maxtmsm Thie For A Release
4. Aveage Time For A Release S. Mnfmum Time For A Releae
6. Total acvt~y for a releases 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Liquid Effluents - Abnormal Release Summary Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 WINS 1ST Quarter 2ND Quater 3RD Quarter 4TH Quarter Yew Totah 0

0 0

0 0

(MInte) 0.00E+00 O.004+00 0.00E+00 0.00E+00 0.00E+00

( Mnutes) 0.006+00 O.006+00 0.00+E00 0M0E+00 0.00E+00 (MInutes) 0.00E+00 0.00E+00 0.00+00 0.00E+00 0.006+00 (Hnutes) 0.00E+00 O.00E+00 0.006+00 O.OOE+00 0.00e+00 (Curies)

O.E0+00 0.00E+00 0.00m+00 O.OO6+00 0.O6o0

.2 pC) 113

0 2.0 Gaseous Effluents 2.1 Regulatory Requirements The ODCM Specifications presented in this section are for Unit I and Unit 2.

2.1.1 Dose Rate Umits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and,

b.

For Iodine-1 31, Iodine-1 33, tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr, to any organ.

2.1.2 Air Doses Due To Noble Gases in Gaseous Effluents The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY, shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b.

During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.3 Doses To A Member of the Public The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from each unit, to areas at and beyond the SITE BOUNDARY, shall be limited to the following.

a.

During any calendar quarter: Less than or equal to 7.5 mrems to any organ.

b.

During any calendar year: Less than or equal to 15 mrems to any organ.

0 2B 114

0 2.2 Measurements and Approximations of Total Radioactivity Waste gas release at Plant Hatch is confined to four paths: main stack (also called the offgas vent), Unit 1 reactor building vent, Unit 2 reactor building vent, and the recombiner building vent. Each of these four paths is continuously monitored for gaseous radioactivity.

2.2.1 Sample Collection and Analysis Each of the four gaseous effluent paths is equipped with an integrating-type sample collection device for collecting particulates and iodines. Unless required more frequently under certain circumstances, samples are collected as follows:

1.

Noble gas samples are collected by grab sampling monthly.

2.

Tritium samples are collected by grab sampling monthly.

3.

Radiolodine samples are collected by pulling the sample stream through a charcoal cartridge over a 7-day period.

4.

Particulates are collected by pulling the sample stream through a particulate filter over a 7-day period.

5.

The 7-day particulate filters above are analyzed for gross alpha activity.

6.

Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the samples are analyzed for Sr-89 and Sr-90.

Sample analysis results and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, the dose rates associated with gaseous releases, and the cumulative doses for the current quarter and year. This task is normally performed with computer assistance.

The noble gas grab sample analysis results are used along with maximum expected release flow rates from each of the four vents to calculate monitor setpoints for the gaseous effluent monitors serving the four release points.

Calculation of monitor setpoints is described in the ODCM. Typically achieved minimum detectable concentrations for gaseous effluents sample and analyses are reported in Table 2-6.

For each release period, released radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated along with the percent of the ODCM limit for each release, for the current quarter and year.

0 29 115

0 2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow:

2.2.2.1 Fission and Activation Gases The released radioactivity is determined using sample analysis results collected as described above and the average release flow rates over the period represented by the collected sample.

Dose rates due to noble gases, radioiodines, tritium, and particulates are calculated (with computer assistance). The calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodine, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.

Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year. Cumulative air doses are compared to the dose limits specified in ODCM 3.1.3. The current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the ODCM.

2.2.2.2 Radioiodine, Tritium and Particulate Releases Released quantities of radioiodines are determined using the weekly samples and release flow rates for the four release points. Radioiodine concentrations are determined by gamma spectroscopy.

Release quantities of particulates are determined using the weekly (filter) samples and release flow rates for the four release points. Gamma spectroscopy is used to quantify concentrations of principal gamma emitters.

After each quarter, the particulate filters from each vent are combined, fused, and a strontium separation is performed. Since sample flows and vent flows are almost constant over each quarterly period the filters from each vent can be dissolved together. Decay corrections are performed back to the middle of the quarterly collection period. If Sr-89 or Sr-90 is not detected, MDC's are calculated.

Strontium concentrations are input into the composite file of the computer and used for release dose rate and dose calculations for a Member of the Public.

0 31 116

Tritium samples are obtained monthly from each vent by passing the sample stream through a cold trap. The grams of water vapor/cubic foot is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed by an independent laboratory and the results are furnished in uCi/mI of water. The tritium concentration in water is converted to the tritium concentration in air and this value is input into the composite file of the computer and used in release, dose rate, and individual dose calculations.

Dose rates due to radiojodine, tritium and particulates are calculated for a hypothetical child exposed to the inhalation pathway at the location in the unrestricted area where the potential dose rate is expected to be the highest.

Dose rates are calculated, for each release point for each release period, and the dose rates from each release point are compared to the dose rate limits as described in ODCM 3.1.2. Doses due to radioiodine, tritium and particulates are calculated for the controlling receptor, which is described in the ODCM. Doses to a Member of the Public are calculated for each release period, and cumulative totals are kept for each unit, for the current calendar quarter and year. Cumulative doses are compared to the dose limits specified in ODCM 3.1.4. The current percent of ODCM limits are shown on the printout for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate filters for each week for gross alpha activity in a proportional counter. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. The summed activity is then divided by the total monthly volume to determine the concentration. This concentration is input into the composite file of the computer and used for release calculations.

2.2.3 Total Error Estimation The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total process of sampling and measurement. Due to the difficulty with assigning error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective is to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.

Estimated errors are associated with counting equipment calibration, counting statistics, vent-flow rates, vent sample flow rates, non-steady release rates, chemical yield factors and sample losses for such items as charcoal cartridges.

31 117

Fission and activation total release was calculated from sample analysis results and release point flow rates.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Non-steady release rates 20%

TOTAL ERROR 65%

1-131 releases were calculated from each weekly sample.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 64%

Particulates with half-lives greater than 8 days releases were calculated from sample analysis results and release point flow rates.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

Total tritium releases were calculated from sample analysis results and release point flow rates.

Water vapor in sample stream determination 20%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 50%

TOTAL ERROR 56%

0 118

Ei Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.

Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non-steady release rates 10%

TOTAL ERROR 63%

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, 1B, and 1C are found in this report as Tables 2-1A, 2-11B, 2-1C, 2-2A,,2-2B, 2-2C, 2-3A, 2-38, and 2-3C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all quarters.

To complete table 2-1A, 2-1 B, and 2-1C, total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/second for each category for each quarter. However, the percent of the ODCM limits are not applicable because we have no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases, and due to radioiodine, tritium, and particulates were calculated as part of the pre-release and post-release permits on individual permits. No limits were exceeded for this reporting period.

Gross alpha radioactivity is reported in Table 2-1A, 2-1B, and 2-1C, as curies released in each quarter.

Limits for cumulative beta and gamma air doses due to noble gases are specified in ODCM 3.1.3. Cumulative air doses are presented in Table 2-4A and 2-48, along with percent of ODCM limits.

Limits for cumulative doses to a Member of the Public due to radioiodine, tritium and particulates, are specified in ODCM 3.1.4. Cumulative doses to a Member of the Public doses are presented in Table 2-5A and 2-51, along with percent of ODCM limits.

0 33 119

2.4 Radiological Impact Due to Gaseous Releases Dose rates due to noble gas release were calculated for the site in accordance with ODCM 3.1.2. Dose rates due to radioiodine, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.1.2.

These dose rates were calculated as part of the pre-release and post release on individual release permits. No limits were exceeded for this reporting period.

Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODOCM 3.1.3. These results are presented in Tables 2.4A and 2-41.

Cumulative doses to a Member of the Public due to radioiodine, trtium and particulates in gaseous releases were calculated for each unit in accordance with ODCM 3.1.4. These results are presented in Tables 2-5A and 2-56.

Dose rates and doses were calculated using the methodology presented in the ODCM.

2.5 Gaseous Effluents - Batch Releases There are no gaseous batch releases from Plant Hatch.

2.6 Gaseous Effluents - Abnormal Releases There were no unplanned or uncontrolled gaseous releases during this reporting period.

34 120

Table 2-lA Q

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Summation Of All Releases Unit: 1 Starting: 1-3an-2014 Ending: 31-Dec2014 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases

1. Total Release Curies 1.55E+00 3.70E-01 2.70E-O1 1.71E+00
2. Average Release rate for period UC/sec 1.96E-O1 4.69E-02 3.43E-02 2.17E-01
3. Percent of Applicable Umit B. Radlolodines L Total Iodine-131 Curies 1.28E-04 1.34E-04 1.18E-04 1.54E-04
2. Average Release rate for period uCIlsec 1.62E-05 1.70E05 1.49E-05 1.95E-05
3. Percent of Applicable Umit C. Particulates L Particulates ( Half-Uves > 8 Days)

Curies 9.59E-06 7.70E-06 1.18E-05 1.44E-05

2. Average Release rate for period uClsec 1.22E-06 9.77E-07 1.49E-06 1.825E-06
3. Percent of Applicable Umit (ID. Tritlum
1. Total Release Curies 2.70E+00 4.31E+00 3.66E+00 3.71E+00
2. Average Release rate for period uCI/sec 3.43E-01 5.47E-01 4.64E-01 4.70E-01
3. Percent of Applicable Limit

.. Gross Alpha

1. Total Release Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0
2. Average Release rate for period uCI/sec O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 0
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

35 121

Table 2-1B Q

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Summation Of All Releases Unit. 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Qusite A. Fission And Activation Gases L Total Release Curies 3.68E+00 3.70E-01 2.70E-01 1.71E+00

2. Average Release rate for period uCI/sec 4.67E-01 4.69E-02 3.43E-02 2.17E-01
3. Percent of Applicable ULimt
a. Radlolodlnes
1. Total Iodine-131 Curies 2.69E-04 1.80E-04 1.64E-04 2.15E-04
2. Average Release rate for period uCi/sec 3.41E-05 2.29E-05 2.07E-05 2.72E-05
3. Percert of Applicable Lmlt C. Particulates
1. Particulates ( Half-Lives > 8 Days)

Curies 1.60E-05 1.25E-05 1.09E-05 1.75E-05

2. Average Release rate for period uC/sec 2.03E-06 1.59E-06 1.39E-06 2.224E-06
3. Percent of Applicable Limit C)D. Tridtum
1. Total Release Curies 7.11E+00 7.12E+00 5.42E+00 5.28E+00
2. Average Release rate for period uOlsec 9.01E-01 9.03E-O1 6.87E-01 6.69E-01
3. Percent of Applicable Limit L Gross Alpha
1. Total Release Curies O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE÷0o
2. Average Release rate for period uOIsec 0.00E+00 0.00E+00 O.OOE+00 O.OOE+O0 0
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.

36 122

Table 2-1C Q

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Summation Of All Releases Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. isuion And Activation Gases 1L Total Release Curles 5.23E+00 7.40E-01 5.41E-01 4.31E+00

2. Average Release rate for period uCl/sec 6.63E-01 9.39E-02 6.86E-02 5.47E-01
3. Percent of Applicable Umit B. Radlolodines L Total lodine-131 Curies 3.97E-04 3.14E-04 2.81E-04 5.02E-04
2. Average Release rate for period uQ3/sec 5.03E-O5 3.99E-05 3.57E-05 6.37E-05
3. Percent of Applicable Umit 2

C. Particulates

1. Particulates ( Half-Uves > 8 Days)

Curies 2.56E-05 2.02E-05 2.27E-05 3.62E-05

2. Average Release rate for period uC/sec 3.24E-06 2.56E-06 2.88E-06 459E-06
3. Peret of Applicable Urt CD.

Tritium

1. Total Release Curies 9.81E+00 1.14E+01 9.08E+00 9.07E+00
2. Average Release rate for period uCi/sec 1.24E+00 1.45E+00 1.1SE+00 1.15E+00
3. Percent of ApplicableUmlt

. Gross Alpha

1. Total Release Curies 0.OOE+00 0.00E+00 0.00E+00 0.00E+00
2. Average Release rate for period uCl/sec 0.00E+00 O.EE+00 O.OOE+OO 0.0E+00 0
  • Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-413, 2-5A, 2-5B of this report.

37 123

Table 2-2A 0

Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Elevated Level Releases Unit: 1 Starting: 1-3an-2014 Ending: 31-Dec-2014 Continuous Mode Nudides Released Fission Gases; Ar-41 Kr-85M Xe-133 Xe-135 Total For Period unit Curies Curies Curies Curies Curies Cniles Curies Curies 1ST Quarter 2ND Quarter 3RD Quarter__1tH Quarter 0.0014.00 2.04E-01 8.39E-01 5.03E-01 L551+0O 4.83E-05 4.95E-05 9.79E-05 0.00E+00 0.00E+00 0.00E+00 3.70E-01 3.70E-01 3.52E-05 7.78E-0 1.13E-04 Iodines 1-131 1-133 Total For Period O.OOE+00 1.04E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.77E-01 2.70E-01 3.94E-01 2.70E-01 L71E+00 3.79E-05 4.88E-05 7.97E-05 1.02E-04 1.18E-04 1.51E-04 O.OOE+00 0.00E+00 0.00E+00 9.71E-08 O.OOE+00 0.OOE+00 6.43E-06 9.85E-06 1.721E-08 2.00E-08 0.00E+00 3.13E-08 9.28E-07 3.10E-06 0.00E+00 O.OOE+00 7.38E-06 1.311-05 Partculates CO-Zn-65 Sr-89 sr-90 CS-137 Ba140 1-131P Curies Curies Curies Curies Curies Curies Curies Curies 7.66E-08 1.30E-07 6.60E-08 4.60E-06 2.58E-08 0.00E+00 2.67E-06 1.13E-07 O.OOE+00 O.OOE+00 O.OOE+00 7.17E-06 2.99E-08 0.00E+00 4.98E-07 O.OOE+00 Total For Period Curies 7.69E-06 7.70E-06 Tritium W3 Curies Curies 1.01E-01 0.00E+00 2.27E-01 O.OOE+00 2.35E-01 3.93E-01 0.00E+00 0.00E+00 Gross Alpha lo Nuclides Found 0

If Not Detected, Nudide Is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

38 124

Table 2-2B 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Elevated Level Releases Unit: 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Continuous Mode Nudides Released Fission Gases Ar-41 Kr-85M Xe-133 Xe-135 Total For Period Unit 1

Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies 9.34E-01 Curies 7.70E-01 Curies 1.33E+00 Curies 6.46E-01 Curioes 3.68E+00 Curies 1.13E-04 Curies 9.39E-05 Curies 2.07E-04 0.00E+00 0.00E+00 0.00E+00 3.70E-01 3.70E-01 3.52E-05 7.78r-05 LU3E-04 O.OOE+00 1.04E+00 0.00+E00 0.00E+00 0.00E÷00 2.77E-01 2.70E-01 3.94E-01 2.70E-01 1.71E+00 3.79E-05 4.88E-05 7.97E-05 1.02E-04 1.18E-04 1,51E-04 lodlums 1-131 1-133 Total For Period, Particulates Zn-65 Sr-89 Sr-90 Cs-137 Bs-140 1-131P Total For Period Curies Curies Curies Curies Curies Curies Curies Curies 7.66E-08 1.30E-07 C60E-08 1.01E-05 5.69E-08 0.00E+00 3.03E-06 1.13E-07 0.001+00 0.00E+00 0.00E+00 7.17E-06 2,99E-08 0.00E+00 4.98E-07 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 6.43E-06 1.721E-08 0.00E+00 9.28E-07 0.00E+00 7.38E-06 2.35E-01 0.00E+00 0.00E+00 9.71E-08 0.OOE+00 9.85E-06 2.001-08 3.13E-08 3.10E-06 0.00E+00 1.31E-05 3.93E-01 0.00E+00 Curfes 1.3GE-05 7.70E-06 Tritium H-3 Gross Alpha No Nucides Found Curios Curies 2.24C-01 0.00E+00 2.27E-01 0.001+00 0

If Not Detected, Nuclide is Not Reported. Zeroes in this table Indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

39 125

Table 2-2C 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Elevated Level Releases Unit-Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Fission Gases Ar-41 Kr-85M Xe-133 Xe-135 Total For Period Nodines 1-131 1-133 Total For Period Unit 5T-Quarter 2ND Quarter Curies 9.34E-01 Curies 9.74E-01 Curies 2.17E+00 Curies 1.15E+00 Curfies 5.23E400 O.OOE+00 O.OOE+00 O.OOE+00 7.40E-01 7.40E-01 7.04E-05 1.56E-04 2.26E-04 Curies Curies Curies 1.61E-04 1.43E-04 3.05E-04 3RD Quarter 4TH Quarter O.OOE+00 2.78E+00 O.OOE+00 0.00E+00 0.00E+00 7391-01 5.41E-01 7.88E-01 SA11E-01 4.31E+00 7.58E-05 1.55E-04 1.59E-04 2.81E-04 2.35E-04 4,35E-04 0.OOE+00 0.OOE+00 0.00E+00 1.94E-07 0.00E+00 0.OOE+00 1.29E-05 2.19E-05 3.44E-08 4.44E-08 0.00E+00 6.26E1-8 1.8W1-06 8.27E-06 0.001+00 0.00E+00 1.48E-05 3.05E-05 Particulates 060 Zn-65 Sr-89 St-90 Cs-137 Ba-140 1-131P Curies Curies Curies Curios curias Curies Curies Curies 1.53E-07 2.60E-07 1.32E-07 1.47E-05 8.27E-08 O.OOE+00 5.71E-06 2.25"-07 O.OOE+00 O.OOE+00 O.OOE+00 1.43E-05 5.97E-08 O.OOE+00 9.95E-07 0.00E+00 Total For Period N-3 Curies 2.13E-05 1.54E-05 Gross Alph No Nuclides Found Curies Curies 3.25E-01 0.00E+00 4.53E-01 0.00E+00 4.70E-01 O.OOE+00 8.72E-01 O.OOE+00 0

If Not Detected, Nucide Is Not Reported. Zeroes in this table Indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

40 126

0 Nudlides Released Fission Gases No Nuclides Found ladines No Nudides Found Particulates No Nudldes Found Tritium No Nuclides Found Gross Alpha No Nudlides Found 0

Unit Curie Cure Cure Curb Curie Table 2-2C Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Elevated Level Releases Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 s

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 0

If Not Detected, Nuclide Is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

41 127

Table 2-3A 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nudides Released Fason Gases No Nuclides Found Unit 1ST quart.

2ND Quarter Curies lodines 1-131 1-133 Total For Period Partliclates Co-60 5(489 Sr-90 Curies curies Curies Curies Curies Curies 0.00E+00 2.58E-05 4.02E-06 2.981-05 0.O0E+00 1.90E-06 0.0OE-e00 1.9OE-06 2.60E+00 0.OOE+00 7.281&06 1.40E-05 2.13E-05 0.OOE+00 1.555-09 5.18E-10 2.06E-09 4.09E+00 3RD Quarter 4TH Quarter O.00E+00 0.00E+00 0.00E+00 2.87E-06 O.OOE+0O 0.00E+00 0.00E+00 2.87E-06 3.30E-06 O.00E+00 1.08E-06 1.29E-06 O.OOE+00 O.00E+00 4,39-06 1.29E-06 3.42E+00 3.31E+00

©1 rotal For Period v

TrItlum H4-3 Gross Alpha No Nudides Found Curies Curies 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0

If Not Detected, Nuclide is Not Reported. Zeroes In this table Indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

42 ill 1I

0 Nuclides Released ssion Gases No Nuclides Found lodines No Nuclides Found Particulates No Nuclides Found Tritium No Nudides Found Gross Alpha 0

No Nucides Found Table 2-3A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 1 Starting: 1-3an-2014 Ending: 31-Dec-2014 Batch Mode Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Curies O.OOE+O1 O.OOE+O0 O.OOE+OM O.OOE+O0 Curies O.OOE+O0 O.OOE+00 0.00E+00 O.OOE)00 Curies 0.00E+00 O.002+00 O.OOE+00

.0.00E+0 0

If Not Detected, Nuclide is Not Reported. Zeroes In this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

43 129

0 Table 2-31 Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Continuous Mode Nudides Released Fission Gases No Nuclides Found Unit Cures LSr Quarter 2ND Quarter O.OOE+00 0.OOE+00 lodines 1-131 1-133 Total For Period Particulates Curies 3.04E-05 Curies 3.18E-05 Curies 6.22E-05 Curies 2-22E-06 Curies 1.68E-07 Curies O.OOE+00 Curies 2.39146 Sr-89 sr-90 1-131P 2i1SE-05 4.54E-05 6.729-05 4.23E-06 0.0mE+00 5.82E-07 4.81E-06 6.89E+00 3RD Quarter 4TH Quarte-0.00E+00 0.00E+00 1.61E-05 1.36E-05 2.99E-05 5.04E-0S 4.59E-O5 6.401-05 3.46E-06 4.23E-06 7.85E-08 0.001+00 0.OOE+00 2-IOE-07 3.54E-06 4.441-06 C1 rotal For Period Tvitlum 11-3 Curies Curies 6.88E+00 0.001+00 5.18E+00 4.88E+00 0.00E+00 0.00E+00 Gross Alpha No Nuclides Found O.OOE+00 0

If Not Detected, Nudide is Not Reported. Zeroes In this table indicates that no radioactivity was present at detectable leveds.

See Table 2-6 for typical minimum detectable concentrations.

44 130

0 Nuclides Released Fission Gases No Nudides Found lodines No Nuclides Found Particulates No Nudides Found Tritium No Nuclides Found Gross Alpha No Nudides Found 0

Table 2-30 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Batch Mode Unit 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Curies O.OOE+O0 O.OOE+O0 O.OOE+OO O.OOE+o0 Curies O.OOE+OO OOOE+O0 O.OOE+O0 O.OOE+O0 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Curies O.OOE+O0 OOOE+O0 O.OOE+00 O.OOE+O0 0

If Not Detected, Nudide Is Not Reported. Zeroes In this table Indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimumr detectable concentrations.

45 131

Table 2-3C 0

Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Fission Gases No Nuclides Found Unit JmrQuarter 2ND Quarter' 3R0 Quarter 4TH Quarter Cures 0.00E+00 0.00E+00 0.00E+00 0.00E400 lodines 1-131 1-133 Total For Period Particulates CO>O Sr-89 Sr-90 1-131P

()otal For Period Tuitium H-3 Gross Alpha No Nuclides Found Curies 5.62E-OS Curies 3.SBE-OS Curies 9.20E-05 Curies 0.00E+00 Curies 4.12E-06 curies 1.68E-07 Curies O.OOE+O0 Curies 4.291-06 2.91E-05 5.94E-05 8.S51-05 O.00E+00 4.23E-06 5.18E-10 5.82E-07 4.81E-06 1.61E-05 1.65E-05 2.99E-05 5.04E-05 4.59E-05 6.6911-05 3.30E-06 0.001+00 4-55E-06 5.S1E-06 7.8SE-08 0.00E+00 0.OOE+00 2.IOE-07 7.9311-06 5.7211-06 Curies Curies 9.48E+00 0.001+00 1.10E+01 0.00E+00 8.61E+00 8.20E+00 0.OOE+00 0.00E+00 0

If Not Detected, Nudide is Not Reported. Zeroes In this table Indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical rninimum detectable cmnCentrato.

46 132

Table 2-3C 0© Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Ground Level Releases Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Nuclides Released Fission,Gases No Nuclides Found Unit 1STQumiter O.O0E+00 Batch Mode 2ND Quarter 3RD Quarter 4TH Quarter lodines' No Nucides Found Particulates No Nuclides Found I

Tritium No Nuclides Found Curies Curies O.O01E+0O O.001E+00 O.OOE+OO O.OOE+OO O.OO1E+O0 O.OOE+OO O.0OE+00 0.OOE+00 O.OOE+00 0.002+00 O.OOE+00 0.00E+00 O.00E+00 0.OOE+00 0.OOE+O0 0.00E+00 0.001E+00 Curies Curies 0

0 iross Alpha 0c Nuclides Found 0.00E+00 O.OOE+00 If Not Detected, Nuclide Is Not Reported. Zeroes In this table indicates that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable conCentrations.

47 133

0 Table 2-4A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Air Doses Due to Gaseous Releases Unit: 1 Starting: 1-3an2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Type of Radituan O0CM Lint Unit 1ST Qtr

%0CM 2ND Qtr _

% D0 3RD Qtr

%00C" 4TH Qtr

% 00CM Gamma Air 5.00.z00 niRad 1.83E-05 3,66C-04 3.90E-06 7.79E-05 5.64E-05 1.13E03 2.16E.04 4.33E-03 BetaAir 1.00E+01 mRad 1.47EO5 L47E-04 1,45E-05 1.4SE-04 4,05E-05 4.05E-04 8.20E.05 6&20E-04 Cumulative Doses Per Year

"-.M o dlmtm 0004 Lnt Units Year to End Dote

%0004 Receptor 1.00E+01 mRad 2.95E-04 2.9SE-03 SITE BOUNDARY I Chd ieta Ai 2.00+E01 mRad 1.52E-04 7.58E-04 MAX IND. AIRORNE / Child Umit Asn Cum Gamma Akdose AM Cue Beta Avdose 48 0

134

0 Table 2-4B Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Air Domes Due to Gaseous Releases Unitb 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quartet Type of Radation 0004 Imt Unl s 1S1 Qtr

% ODCH 2wo qtr

% 000C 3RD Qtr

% 00CM 4TH Qtr

% 00CM Gamma Air S.OE÷00 mRand IMfE-05 3.73E-04 3.90E-06 7.79E-0 S.64E-OS i.13E-03 2.16E-04 4.33E-03 Beta Ai 1.00E+0L mRad I.51E-05 1.51E-04 1.45E-05 1.45E.04 4.OSE-05 4.05E-04 8.20E-05 8.20E-04 Ctmulative Doses Per Year 00CM ofLausatikn OnC1 Lmt Un.ts Yea to End Date

% 0004 Receptr Air 1ooi A,*+0 rd 2.95E-04 2.9SE-03 SITE BOUNDARY I Chfld

-leta Air 2.OOE+01 na"d 1.52E-04 7.60E-04 MAX I*D. AIRBORNE / Child unit Ann Cuun Gamma Akdose Afm Curm eta Akdose 49 0

135

0 Table 2-5A Hatch Nuclear Plant RADIOACITYN EFFLUENT RELEASE REPORT - 2014 Doses To A Member Of The Public Due To Radlodines, Trtlun, and Partculates In Gaseous Releases Unit: 1 Starting: 1-Jan-2014 Ending: 31-Dec-2014 Cumulative Doses Per Quarter Organ ODEM Lot uShts ISTQ tr 0OCH

-MW Qr

%000C 3R1 Qtr

% ODCH 4TH Wtr

% *00C Total Body 7.50E+00 mRem 1.3SE-03 1.8-02 21-03 2.83E102 1.8E-03 2.40E-02 1.72E,03 2.30E-02 Lung 7.50E+00

mRe, 1.35E-03 1.802-02 2.12E-03 2,82E-02 1.80E-03 2.40E-02 1.72E-03 2.29E-02 ThyId 7.506+00 mRem 1.84E-03 2.45E-02 2.31E-03 3.082-02 1.886.03 2.50E-02 i.872-03 2.49E-02 Bone 7.50E+00 mRem 2.96E-05 3.94E-04 137E-05 1.83E-04 4.20E.05 5.61E-04 3.0-OE05 4.02E-04 LIve 7.502+00 mraela 1.35E243 1.80E-02 2.12E-03 2.83E-02 I.80E-03 239E-02 L72E-03 2.29E-02 7.502+00 mftem L.35E-03 1.80E502 2.12E-03 2.83E802 1.80"-03 2.39E-02 1.72E.03 2.29E-02 7.SO-+00 mRnln 135E203 1.80E-02 2.12E-03 2.83E-02 1.80E-03 2.40E-02 1.72F-03 22N9-02 Cumulative Doses per Year Organ 00CM Lint Units aw to Ending Date

% 0001 Receptor Limit liver 1.500f+01

a7 6.985E-03 4.7566-02 MAX 11D. AIRBORNE / Cld An Cn u

od/Pad Akdose Total Body I.5002+01 nRn 6.988-03 4.659F-02 MAX IND>.

AIRBORNE I Chld Ann Cumn la/Pai AIkdose Lung 1.5002.01 mRem 6.985E.03 4.657E-02 MAX IND, AIRBORNE / Child Ann Cumr [oa/Prt Akrdase G-UN 1.5002+01 milan 6.987E.03 4.6582-02 MAX IND. AIRBORNE / Child Ann Cur xod/Part Aide KiXMey I.500+01 MIlan 6.986E-03 4.657E-02 MAX IND. AIRBORNE / Child Ann Cumr loaf~art Abdose ThRMoRd 1.500E+01 mlemn 7.698E.03 5,2656-02 MAX IND. AIRBORE / ChIld Ann Curn IoVPt Alrdose Bone 1.500+01 mitern 1.155E.04 7.698f-04 MAX IND. AIRBO*N

  • Child Ann Crn ld/Part Akrdose 60 0

136

0 Table 2-58 Hatch Nuclear Plant RADIOACTVE EFFLUENT RELEASE REPORT - 2014 Doses To A Member Of The Public Due To Radlolodines, Tritium, and Particulates In Gaseous Releases Unit: 2 Staring: 1-Jan-2014 Endingt 31-Dec-2014 Cumulative Doses Per Quarter aga 00 Int Lag ts WSi wqir

%O OCi 2ND Qt

% ODC4 3RD Qtr

% 0DC4 44TH Qbr

% 000C Lung 7.50,E00

Z;-

3.57E-03 4.765-02 3.575-03 4.76-02 2.69.03 3.58-02 2.53E503 3.38E.02 Total Body 7.501+00 mraem 3.58E-03 4.78E-02 3.57E-03 4.766-02 2.70E-03 3.59E-02 2.54E.03 3312-02 Bone 7.50E+00 mRern 1.04E-04 1.39-03 5.70E-05 7.60E.04 7.52E.05 1.001E03 6.055E05 8.07E-04 Kldney 7.50M+00 minten 3.57E-03 4.76E-02 3.57E-03 4.76E-02 2.69E-03 3.58E.02 2.53E-03 3.38E-02 UV 7.50+00 nane 3.57E-03 4.76E-02 3.57E503 4.76E-02 2.69E-03 3.58M-02 2.53E.03 3.38E-02 C

7.56]7+00 miean 3.57E-03 4.76E-02 3.57E-03 4.76E-02 2.69E.03 3.59E-02 2.54E-03 3.38E-02 7

7.50E+00 maem 4.285-03 5.70E-02 4.005-03 5.33E.02 3.03E-03 4.041-02 2.87E-03 3.83E-02 Cumulative Doses per Year oran O0c0 Lint Units Year to Endin Date

% ODCM Rempto Lhnlt Aung

.5005+01 mRem 1.236E-02 8.239E-02 MAX 114N.

AIRBORNE C hild Ann Cumr Iod1'art Airdae G.LN 1.580+E401 miem 1.236E-02 8.243E-02 MAX 11ND.

AIRBORNE I Child Ann Cmn [od/Part Airdose Total Body I.5006+01 mRem 1.239E-02 8.25-02 MAX IND. AIRBORNE / ChlI Ann Cum alcd/PaM Ardose LlvV 1.500+0I mn 1.236E,02 8.24JE-02 MAX 1ND. AIRBORNE/ Child Ann Cum 1o0ParM Ahlrte K

y 1.500+01 nmRem 1.236E-02 8.243E-02 MAX 1IN. AIRBORNE I Odld Ann Caren Woc/art AWo Bone I.S008+01 rntew 2.968E-04 1.9791-03 MAX IND. AIRBORNE / Cild Ann Car Iod/Part Airdose Thyroid 1.5005+01 mRem 1.415E-02 9.453E-02 MAX IND. AIRBORNE I Child Arn Cur lod/Part Ardose 51 137

0 TABLE 2-6 E. L. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT-2014 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES STARTING: 1-Jan-2014 ENDING: 31-Dec-2014 The values in this table represent a prori Minimum Delectable Concentration (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 2.94E-08 uCilcc Kr-88 3.22E-08 uCilcc Xe-133 2.30E-05 uCilcc Xe-133m 7.30E-08 uCilcc Xe-135 8.73E-09 uCi/cc Xe-138 1.99E-07 uCilcc 1-131 1.34E-13*

uCt/cc 1-133 1.53E-13*

uCi/cc Mn-54 1.62E.13" uCilcc Fe-59 3.42E-13" uCi/cc Co-58 1.30E-13" uCi/cc Co-60 1.54E-13" uCilcc Zn-65 2.54E-13*

uCi/cc Mo-99 9.61E-13*

uCi/cc Cs-134 1.42E-13" uCi/cc Cs-137 1.28E-13*

uCi/cc Ce-141 1.26E-13*

uCuicc Ce-144 5.64E-13" uCi/cc Sr-89 1.10E-16 uCi/cc Sr-90 6.70E-16 uCiucc H-3 4.OOE-07 uCi/cc Based on an estimated sample quantity of 4.078E+07 cc s.

52 0

138

0 Table 2-7A Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -2014 Gaseous Effluents - Batch Release Summary unit: 1 starting: 1-3an-2014 Ending, 31-Dec-2014 Gaseaus Reease

1. Murnber of balch releame
2. Toa tUne period for batc MeWleS
3. m148urn ime period fo a batch release
4. Average ImUe period for a batch release
5. Mbnum tble period for a batch release Unhs S5T quarter 0

(mtintes) o.0o0+00 (fblntes) 0,00E+00 (Minutes) 0.00E+00 (Mhiutes)

O.OOE+00 2ND Quares' 3RD Quarter 4TH Quarter Year Totals 0

0 0

0 O.OOE+O0 0.00E+00 O.OOE+00 OOOC-+OD 0.002-+00 0.00f+00 0.00E+00 O.OOE+G0 MO.OE+O0 0.00E+00 0.00+00 0.002400 0.00E+00 O.ODE+O()

0.00E+00 0.00E+80 0

139

0 Table 2-70 Hatch Nudlear Plant RADIOACFKVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - match Release Summary Unit: 2 Startingi 1-Jan.2014 Ending: 31-Dec-2014 Canmms Ree~

1. Number of batch eases
2. Toale Sne p eriodr bacht releases
3. Maxirman tie period for a bath elease
4. Average tuie period for a belch release S. MlWiman lime period for a bath release thf ST wQurter 0

(minutes) o.ooE+00

( MkVtes) o.oE+00 (Minutes)

O.O0E+o0 (Minutes)

O.0Ev+00 21D Quarter 0

0.001+00 0.001+00 O.OOE.00 3RD Quairter a

0.00E+00 0.00E+00 0.00E+00 0.005.00 4TH Quarter 0

0.00E+00 O.OOE4+00 0.00E+00 YearlToas 0

0.00E+00 O.OOE+00 O.OOE+00 O.OOE+O0 0

54 (C

140

0 Table 2-8A Watch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Abnormal Release Summary Unit.' 1 Starting: 1-3an-2014 Ending: 31-Dec-2014 Gaseous Releases L Nlme* of Releases

2. Total Toem For Al Releases
3. M#keluni TI*e For A Release
4. Average lime For A Release
5.

Imulmn Thime Fos A Release

6. Total activity for all releases UWits in' Quarter 0

(Minutes) 0.009+00 (Minutes)

O.OE,.00 (Mbultes) 0.00E+00 (Miutes) 0.00E+00 (Curies) 0.00E+00 2ND Quarter 3RD Quarter 4TH Quarter Year Totals 0

0 0

0 O.OOE+O0 0.0AM+00 0.00M400 O.OOE+00 O.O0E+O0 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.006+00 0.009+00 0.00E+01 9.00E+00 0.00E+00 O,OOE+00 0.009-+00 0.00E+00 0.00E+00 0.00E+00 55 0

141

0 Table 2-811 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Abnormal Release summary Unit: 2 Starting: 1-3an-2014 Ending: 31-Dec-2014 CaSeous Releases

1. Number ol Releases Z. TOa Time For Al Releases
3. Maximum Time For A Release
4. Average Time FOr A Release S. MInum Time For A Release O
6. ToWal ectlvy for a, releases Units 1ST Quartem 0

(NMkutes) 000E+00

(

~iutes

)

0.00E,00 (Mtnutes) 0.00E+00

( Mutes )

0.00E+00 (Cwles) 0.00E+00 2ND Quarter 0

0.00w.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3R0 Quate 0

0.00E+00 o 00E+0o O.DOE+0D 0.00E+00 0.100+00 4TH quarter 0

0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 YearTotals 0

O.00E+00 0.0O+00 O.00E+00 O.OOE400 O.OOE+00 so 0

142

Table 2-8C Hatch Nudlear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Gaseous Effluents - Abnormal Release Summary Unit Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Gaseous Releases I. NMnter or Releases

2. Total Time For All Releases
3. Hdaknwu Tr* For A Release
4. Average Time For A Release
5. Mlnnum Thm For A Release
6. Total adty for al releases tnits 1ST Quarte 0

(Minutes)

(Minutes)

(MIAes)

(Minutes)

(Cures) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2ND Quarter 0

0.00E+00 O.OOE+GO 0.006,.00 O.OOE

,+00 0.00E+00 0.001F+00 3RD Quarter 4TH Quarter Year Totals 0

0 0

0.009+00 0.006+00 0-00E+00 0.006+00 0.00E+00 0.00E+00 0.00 1)0 0.00E+00 000E+00 0.00f+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Si 143

3.0 Solid Waste 3.1 Regulatory Requirements The Process Control Program (PCP) and the ODCM requirements presented in this section are for Unit I and Unit 2 and are stated in part.

3.1.1 Solid Radioactive Waste System PCP Section A.3.1 Solid Radioactive Waste System control states:

The solid radwaste system shall be used in accordance with the PROCESS CONTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure that they meet requirements of 10 CFR Parts 20 and 71, prior to shipment of radioactive wastes from the site.

3.1.2 Reporting Requirements Technical Specification 5.6.3 requires in part:

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

PCP Section A.4.1 states in part:

The Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shall include a summary of the quantities of solid radwaste released from the units as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a 6 month basis following the format of Appendix B thereof.

58 144

For each type of solid radwaste shipped offsite during the report period, the report shall include the following information:

a.

Container volume.

b.

Total curie quantity (specify whether determined by measurement or estimate).

c.

Principal radionuclides (specify whether determined by measurement or estimate).

d.

Type of waste (such as spent resin, compacted dry waste, evaporator bottoms).

e.

Type of container (such as LSA, type A, type B, large quantity).

f.

Solidification agent (such as cement).

Major changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed and accepted by the PRB.

3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1.

59 145

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT I AND 2 STARTING: 1-Jan-2014 ENDING: 30-Jun-2014 A QnI Inl UUA.QTI QW1IDDrfl n=1-qT= Cn fI PIAI nQ n1Q~DA I thd~ irr=Aia el~~

fmrnIl

1. Type of waste UNIT 6 month Est. Total period ERROR %
a. Spent resins, filter sludges, evaporator m_

3.93E+01 bottoms, etc.

Ci 3.97E+02 1.00 E 01

b. Dry compressible waste, contaminated equip.

m 7.48E+02 etc.

Ci 2.00E-01 2.00E01

c. Irradiated components, control rods, m3 Ci
d. Control Rod Drive Filters m_

1 Ci

e. Other (describe) m Equip. etc.

Ci

2. Estimate of major nuclide composition (by type of waste)

ISOTOPE PERCENT CURIES a.Fe-55 9.8 3.90E+01 Co-60 47.9 1.90E+02 Zn-65 14.0 5.57E+01 Mn-54 18.0 7.14E+01 Cs-137 1.1 4.18E+00 Cr-51 1.8 6.94E+00 Other 7.6 3.01E+01 b.Fe-55 62.8 1.25E-01 Co-60 15.6 3.21E-02 Mn-54 4.59 9.16E-03 Zn-65 2.13 4.26E-03 Other 14.9 2.98E-02 C.

d.

e.

4 4

.1

3. Solid Waste Disposition Number of Shipments Mode of Transportation All waste sent to processors NIA B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation 0

N/A 6o Destination N/A Destination N/A 146

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 SOLID WASTE AND IRRADIA TED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1-JuI-2014 ENDING: 31-Dec-2014 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste UNIT 6 month Est. Total period ERROR %
a. Spent resins, filter sludges, evaporator m7 4.73E+01 bottoms, etc.

Ci 2.58E+01 1.00 E 01

b. Dry compressible waste, contaminated equip.

m_

3 2.02E+03 etc.

Ci 3.05E+00 2.00 E 01

c. Irradiated components, control rods, m

Ci

d. Control Rod Drive Filters m
e. Other (describe) m Equip. etc.

Ci..

2. Estimate of major nuclide composition (by type of waste)

ISOTOPE PERCENT CURIES a.Fe-55, 24.6 6.35E+00 Co-60 33.9 8.74E+00 Zn-65 5.3 1.36E+00 Mn-54 7.9 2.04E+00 Cs-137 6.1 1.58E+00 Cr-51 0.0 O.OOE+00 Other 22.1 5.71 E+00 b.Fe-55 62.8 1.91E-00 Co-60 15.6 4.74E-01 Mn-54 4.6 1.40E-01 Zn-65 2.13 6.49E-02 Other 14.9 4.54E-01 C.

d.

e.

3. Solid Waste Disposition Number of Shioments Mode-of Transoortation All waste sent to processors N/A B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation 0

N/A Destination N/A Destination N/A 61 147

TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT-2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT I AND 2 STARTING~: 1-Jan.2014 ENDING: 30-Jun.2014 I-a

-21 EN IG 3

J.......

TYPE CURK PRINCIPAL BURIAL NUMIBER OF VOLUME OF TYPE SHIPMENTI SOLIDIFICATION OF QUANTWTI NUCLIDESI CONTAINER CONTAINERS EACH CONTAINER AGENT WASTE OVTERHINEO DETERMINATION DESCRIPTION SHIPPED CONTAINER CUBI FEET Dewatered 39.6 Zn-5.Fe-55.Co-60 Carbon 8

195 NIA Resins Mn-54, Cr-51 Steel 14-210 DOT7A 120.3 TypeA CasW Une~s/(eXNMa) 8-12018 Type 8 Poly HIe Sippir Cask Dry 0.200 Fe-55,Co-N0.Mn-S,4 8.25 57 90/

WIA Actie Waste Zn-65 Boxewhligh See Noe 2080 Geneal Design Integity (8-25y Sealands Container (IP-1)

  • Note: The actual size and number of the containers may vary from the recorded values due to the use of different containers by waste processors.

STC-Strong Tight Container TABLE 3-1 E. I. HATCH NUCLEAR PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS UNIT 1 AND 2 STARTING: 1.JUIL.2014 ENDING: 31-DEC-2014 TYPE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SHU ENTI SOLIDIFICATION OF OUANITYI NUCLIDES!

CONTAINER CONTAINERS EACH CONTAINER AGENT WASTE DETERMINED DETERMINATION OESCRIPTION SHIPPED CONTAINER CUBIC FEET Irr In Dewaered 258 Zn-65Fe-55oCo-60 Carbon 9

195 14-210 DOT 7A WA Resins Mn*4, Crr51 StW4 i*ners TYPE A CASK (external)

Dry 3.05 Fe-55.CG-W.1n-5d W25 Boxes/

Genr~aJ On'g Hqgh Ints 93 95rdW0 02-$)J Se,*wW NI*A Act Wast zn,6$

Coamel

'Sao Noeo 6401195 M.AIW Poly H*C Type A CA 62 148

4.0 Doses to Members of the Public Inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part that the Radioactive Effluent Release Report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with the ODCM.

4.2 Demonstration of Compliance The locations of concern within the site boundary are the Roadside Park, the Camping Area, the Recreation Area, and the Visitors Center. Listed in Table 4-1 are: The distance and direction from a point midway between the center of Unit I and the Unit 2 reactors, the dispersion and deposition factors for any releases from the Main Stack (elevated) and from the reactor building (ground level); and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.

The source term is not listed in Table 4-1. The source term is listed in Tables 2-2A and 2-2B, for the elevated releases. Similarly the source term is listed in Tables 2-3A and 2-3B for the ground level releases.

The maximum doses in units of mrem accumulated by an individual MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period are presented in Table 4-1.

63 149

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1o-an-2014 Ending: 31-Dec-2014 Location Name:

Distance (kilometers):

Sector.

Occupancy Factor:

Age Group:

Ground Level Release Ground Level Release Elevated Release Elevated Release ROADSIDE PARK 1.18E+00 WNW 2.28E-04 Child Particulate and Radiloodine Noble Gas Particulate and Radioiodine Noble Gas X/Q (sec/m3): 7.OOE-06 X/Q (Seclmn3): 7.83E-06 X/Q (sec/m3): 2.37E-08 X/Q (sec/m3): 2.42E-08 Thyroid Total Body Lung GI-Li Skin Bone Liver Kidney Units 1ST Quarter mRem 5.95E-09 mRem 5.41E-09 mRem 5.41E-09 mRem 5.41E-09 mRem 2.87E-12 2ND Quarter 6.62E-09 6.26E-09 6.27E-D9 6.26E-09 1.32E-12 3.65E-12 6.26E-09 6.26E-09 3RD Quarter 5.21E-09 5.OIE-09 5.03E-09 5.01E-09 1.22E-10 1.10E-10 5.GIE-09 5.01E-09 DIQ (mi-2): 2.01lE-08 DIQ (mi-2): 1.29E-09 4TH Quarter Year 4.92E-09 2.27E-08 4.68E-09 2.14E-08 4.68E-09 2.14E-08 4.68E-09 2.14E-08 1.65E-12 1.28E-10 3.93E-12 1.32,E-10 4.66E-09 2.14E-OB 4.68C-09 2.14E-08 mRemn mitem mitem 1.40E-11 5.4 1E-09 5.41lE-09 64 150

Table 4-1 Hatch Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Location Name:

Distance (kilometers):

Sector:

Occupancy Factor.

Age Group:

Ground Level Release Elevated Release Ground Level Release Elevated Release CAMPING AREA 1.27E+00 WNW 5.48E-03 Child Particulate and Radlolodine Particulate and Radiolodine Noble Gas Noble Gas X/Q (sec/m3): 6.27E-06 X/Q (sec/m3): 2.33E-08 XIQ (seclm3): 7.03E-06 X/Q (sec/l3): 2.38E-08 D/Q (m-2): 1.80E-08 D/Q (m-2): 2.01E-08 TOW Body Thyrd GI-Ui Liver Lung Skin Bone Kidney Units mRem mRem mRemn mRem mRem mRem mRem mRem 15T Quarter 1.17E-07 1.28E-07 1.17E-07 1,17E-07 1.i7E-07 4.20E-10 6.02E-10

1. 17E-07 2ND0 Quarter 1.35E-07 1.43E-07 1-35E-07 1.35E-07 1.35E-07 9.31E-11 1.32E-10 1.35E-07 3RD Quarter L.GBE-07 1.12E-07 1.08E-07 1.08E-07 1.08E-07 2.70E-09 2.43E-09 1.08E-07 4TH Quarter I.OtE-07 1.06E-07 I.0IE-07 1.01E-07 1.O1E-07 3.66E-10 3.62E-10 1.01E-07 Year 4.61E-07 4.89E.07 4.61E-07 4.61E-07 4.61F-07 3.58E-09 3.52E-09 4.61E-07 65 151

Table 4-1 Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit, Site Starting: 1-Jan-2014 Ending: 31-Dec-2014 Location Name:

Distance (kilometers):

Sector.

Occupancy Factor.

Age Group:

Ground Level Release Elevated Release Elevated Release Ground Level Release RECREATION AREA 1.03E+O0 SSE 2.37E-02 Child Particulate and Radiolodine Noble Gas Particulate and Racdolodine Noble Gas X/Q (sec/m3): 5.73E-06 XIQ (sec/m3): 3.30E-08 XIQ (sec/m3): 3.21E-08 X/Q (sec/m3): 6.42E-06 D/Q (mn-2): 2.36E-08 DIQ {mn-2): 1.56E-09 Bone Lung Skin Uver Thyrold Total Body Kidney GI-Ui Units mRern mRern mRem mRem mRem mrftem mRem mRem J1ST Quarter 1.28E-09 4.61E-07 3.54E-10 4.61E-07 5.06E-07 4.61E-07 4.61E-07 4.60E-07 2ND Quarter 3.53E-10 5.33E-07 1.62E-10 5.33E-07 5.63E-07 5.33E-07 S.33E-07 S.33E-07 3RD Quarter 1.32E-08 4.32E-07 1.49E-08 4.30E-07 4.47E-07 4.30E-07 4.30E-07 4.30E-07 4ITH Quarter Year 3.91E-10 I.S2E-08 3.99E-07 1.82E-06 2.05E-10 1.57E-08 3.98"-7 1.82E-06 4.19E-07 1.94E-06 3.98E-07 1.82E-06 3,98E-07 I.S2E*06 3.98E-07 1.82E-06 66 152

Table 4-1 Hatch Nudear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2014 Doses to a Member of the Public Due to Activities Inside the Site Boundary Unit: Site Starting: 1-3an-2014 Ending: 31-Dec-2014 Location Name:

Distance (kilometers):

Sector.

Occupancy Factor.

Age Group:

Ground Level Release Elevated Release Elevated Release Ground Level Release VISITORS CENTER 6.94E-01 WSW 4.57E-4.

ChIld Noble Gas Particulate and Radiolodine Noble Gas Particulate and Radioiodine

)X/Q (sec/m3): 1.87E-05 XIQ (sec/m3): 4.97E-08 X/Q (sec/'m3): 5.O0E-08 X/Q (sec/m3): 1.72E-05 DIQ (mi-2): 2.26E-09 DIQ (mn-2): 5.47E-O6 Liver Total Body Lung GI-Ui Bone Thyroid Kidney Skin Units mRem mRem mRem mRem mRem mRem mRem mRem 1ST Quater 2.66E-08 2.66E-08 2.67E-08 2.66E-08 6.84E-11 2.93E-08 2.67E-08 1.37E-11 2ND Quarter 3RD Quarter 4TH Quarter Year 3.08E-08 2.47E-08 2.30E-08 1.05E-07 3.08E-08 2.47E-08 2.30E-08 1.05E-07 3.09E-08 2.48E-08 2.31E-08 l.05E-07 3.08E-08 2.47E-08 2.30E-08 1.05E-07 1.82E-11 5.97E-10 1.85E-11 7.02E-10 3.26E-08 2.57E-08 2.42E-08 1.12E-07 3.08E-08 2.47E-08 2.30E-08 1.05E-07 6.87E-12 6.67E-10 7.20E-12 6.95E-10 67 153

5.0 Total Dose from Uranium Fuel Cycle (40 CFR 190) 5.1 Regulatory Requirements The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

5.2 Demonstration of Compliance No dose limits stated in ODCM Sections 2.1.3, 3.1.3, and 3.1.4 were exceeded.

Therefore, compliance with 40 CFR 190 dose limits was demonstrated in accordance with the requirements of ODCM Section 5.1.3.

68 154

I 6.0 Meteorological Data The Radioactive Effluent Release Report, to be submitted by May 1 of each year, shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured), on magnetic tape, or, in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

In lieu of submission with the Radioactive Effluent Release Report, the licensee has retained this summary of required meteorological data on site, in a file. It will be provided to the NRC upon request.

155

7.0 Program Deviations 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirements ODCM, Chapter 7, Section 7.2.2.6.2 states that the Radioactive Effluent Release Report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively.

7.1.2 Description of Deviations There was one deviation from the liquid and gaseous effluent monitoring instrumentation operability requirements during this reporting period.

The Main Stack Effluent flow instrumentation was non-functional for > 30 days.

The flow instrument was declared OOS when it was changed out for a newer rotometer and the humidity at the Main Stack was not taken into account on the new instrumentation. Flow estimations were performed by chemistry techs. The instrumention was OOS from 11/30/14 until 17311/14. (RAS 1-14-312) 7.2 Tanks Exceeding Curie Content Limits 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include notifications if the contents within any outside temporary tank, for liquids, exceed the limit of Technical Specification 5.5.8.b.

7.2.2 Description of Deviations There were no outside temporary tanks, for liquids, that exceeded the limit of Technical Specification 5.5.8.b during this reporting period.

70 156

7.3 Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC) 7.3.1 Regulatory Requirements ODCM 7.2.2.6 states in part that deviations from MDC(s) required in Table 3-3 shall be included in the Radioactive Effluent Release Report.

7.3.2 Description of Deviation There were no deviations from MDC(s) required in Table 3-3 during this reporting period.

8.0 Changes to the Plant Hatch Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements Pursuant to Technical Specification 5.5.1 and ODCM Section 7.2.2.5, licensee initiated changes shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

8.2 Description of Changes There were no changes to the Hatch ODCM in 2014.

71 157

9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 9.1 Regulatory Requirements The Radioactive Effluent Release Report shall include any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to ODCM Chapter 7, Section 7.2.2.7.

9.2 Description of Major Changes Gaseous Radwaste System There were no major changes to the gaseous radwaste system during this reporting period.

Solid Radwaste System There were no major changes to the solid radwaste system during this reporting period.

Liquid Radwaste System There were no major changes to the liquid radwaste treatment system during this reporting period.

72 158

SOUTHERN COMPANY E. L HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT JANUARY 1, 2014 - DECEMBER 31, 2014 APPENDIX A 73 159

Hatch Nuclear Plant Appendix A CARBON-14 Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half-life. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.

As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of "principal radionuclides" in gaseous effluents have changed, and C-14 has become a larger percentage. "Principal radionuclides" are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21),

"Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants will report C-14 amounts released and resulting doses to the maximally exposed member of the public.

Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation. The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.

At Plant Hatch, the quantity of C-1 4 released in gaseous effluents in 2010 was estimated to be 14.16 Curies (per unit). Approximately 95% of the C-14 released is in the form of 14CO2 and is incorporated into plants through photosynthesis. Ingestion dose results from this pathway. The remaining 5% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Hatch ODCM, the resulting bone dose to a child located at the controlling receptor location would be 1.59E-01 mrem in a year which is 1.06% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents. The resulting total body dose to a child located at the controlling receptor location would be 3.18E-02 mrem in a year which is 0.21% of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents.

74 160

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO. 1 & 2 ANNUAL REPORT JANUARY 1, 2014 - DECEMBER 31, 2014 APPENDIX B 7s 161

Appendix B Summary of Groundwater Protection Program Nuclear Management Procedure NMP-EN-002 provides the methodology and criteria for implementation of the Radiological Groundwater Protection Program (GWPP) including evaluating hydrology and geology, conducting a risk assessment, establishing and modifying on-site ground water monitoring, voluntary communications, corrective actions, reporting, and record keeping. Each program element of NEI 07-07 "Industry Ground Water Protection Initiative - Final Guidance Document" is identified in the corresponding procedure element.

At Plant Hatch procedure 64CH-SAM-028-0 Releases Via Planned and Unplanned Routes: Sampling and Analysis procedure provides instructions for the sampling of groundwater sample wells, drainage outfalls, STP effluent and drinking water deep wells for the Releases via Unplanned Routes (RVUR) sampling and analysis program.

The Attachments to 64CH-SAM-028-0 contain the maps of the sampling points, the locations, collection frequency and the analyses required.

76 162

Retrieved from "https://kanterella.com/w/index.php?title=ML15125A056&oldid=5191340"